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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
Jun-Yi Zhang, Xiao Yan (CNNC Key Laboratory on Reactor Thermal Hydraulics Technology), Ze-Jun Xiao (Hualong Pressurized Water Reactor Technology Corporation, Ltd.), Yong-Ze Xu (CD-adapco)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1134-1143
Subcooled boiling heat transfer, which is related to Departure of Nucleate Boiling(DNB), is highly concerned in fuel assembly of PWR. It is of importance and significance to predict void fraction and mass/energy transfer characteristics among sub-channels under subcooled boiling with 3-D CFD code to obtain more details for better understanding of two-phase flow process in rod bundle. To better understand and predict void distribution and its transportation characteristics in rod bundle, two-phase flow simulation with two-fluid model was carried out with Heat Partitioning Model. In this study, the 5×5 full length PSBT rod bundle with Uniform-Axial Power Distribution (U-APD) was used under prototype condition (test serial of B5 configuration) to test the physical method. The parameter distribution in axial and radial orientation among different sub-channels at the downstream of the last Mixing Vane Grid(MVG), where the DNB occurs at the end of the heated section, was studied. Different void fraction distribution was observed among central channels, side channels and corner channels. It is induced by different mass transfer process results from the layout of mixing vanes. Moreover, different mass transfer characteristics occurred between corner channels at the different location. Energy transfer is related to the mass transfer among sub-channels. The simple support grid (SSG) shows a suppression of radial transverse flow which is introduced by the mixing vanes for heat transfer enhancement.